Securing the safe performance of graphite reactor cores / edited by Gareth B. Neighbour
- Published
- Cambridge : Royal Society of Chemistry, [2010]
- Copyright Date
- ©2010
- Physical Description
- xi, 259 pages : illustrations ; 25 cm.
- Additional Creators
- Neighbour, Gareth B., Royal Society of Chemistry (Great Britain), and British Carbon Group
- Series
- Contents
- Part A. General Introduction -- A Look into the Past - How it all Began / Derek Dominey -- The Development and Application of a Protocol for the Validation of Core Component Condition Assessment Prediction Methods / Iain Roberson -- Part B. Assessing Core Behaviour and Methodologies -- Application of Whole Core Modelling Methodology with Representative Core Loading to Life Extension of AGR Graphite Cores / Calum Powrie -- Assessment Methodologies for Simulation of Control Rod Movements in an Ageing Graphite Core / Neil McLachlan -- IMAPS - A System for Managing Graphite Core Information / Stephen D. J. McArthur -- On Non Smooth Contact Dynamics Methodology for the Behaviour Assessment of Discontinuous Blocky Assemblies / Tomasz Koziara -- Two Dimensional Analysis of AGR Core using a Super-Element Technique / Graham B Heys -- The Applicability of the Equivalent Temperature Concept for the Correlation of Graphite Dimensional Change Behaviour in Magnox Reactor Cores / John F. B. Payne -- Underwriting the Weight Loss Limit for Graphite in AGR Power Stations / Peter J. Geering -- Part C. Surveillance and Test Methods -- BETA: A System for Automated Intelligent Analysis of Fuel Grab Load Trace Data for Graphite Core Condition Monitoring / Dave Towle -- Volumetric Inspection of Reactor Core Graphite Using Eddy Currents / Matthew Brown -- A Statistical Analysis of the Mechanical Properties of PGA Graphite Samples taken from Magnox Nuclear Reactors / Barry J. Marsden -- Understanding AGR Graphite Brick Cracking using Physical Understanding and Statistical Modelling / Alan G. Steer -- Development of Dynamic Young's Modulus Test Setup for Irradiated and Oxidised Graphite / Onne Wouters -- Stress Measurment in Porous Graphite at Different Scale Lengths / David J. Smith -- Mechanical and Thermal Property Measurements on AGR Core Graphite Using Electronic Speckle Pattern Interferometry / John G. Gravenor -- Pile Grade A Graphite - Poisson's Ratio / Colin D. Elcoate -- Derivation of Dimensional Change Behaviour from Irradiated Brick Geometry / John F. B. Payne -- Biaxial Testing: Appropriate for Mechanical Characterisation? / Gareth B. Neighbour -- Part D. Prediction of Component Performance -- The Development of a Microstructural Model to Evaluate the Irradiation Induced Property Changes in IG-110 Graphite using X-ray Tomography / Kazuhiro Sawa -- A Consideration of the Effect of Radiolytic Oxidation on Fracture Behaviour of Reactor Core Graphites / Peter E. J. Flewitt -- Stress Concentration Factors for Magnox Moderator Graphite / Martin Lamb -- Using First Principles Calculations to Estimate Thermal Properties of Graphite and its Defects / Malcolm Heggie -- Irradiation Induced Creep in Nuclear Graphite - Present Status and Near Future Activities / Gerd Haag -- Part E. Plant Performance -- Continuing Development of the Quarter Scale Core Rig to Support the Safe Performance of Graphite Reactor Cores / Neil McLachlan -- The Effect of Reactor Parameters on AGR Refuelling at Hinkley Point B / James Reed -- Part F. Graphite Reactor Decommissioning -- Twenty-First Century Solutions to the Graphite Dismantling and Radwaste Problems / David Bradbury -- Should Subjective Risk be taken into Account in the Design Process for Graphite Disposal? / Robert Price -- The Location of Radioisotopes in British Experimental Pile Grade Zero Graphite Waste / Anthony J. Wickham -- Radioactive Gas Generation and Containment in ILW Repositories / Michael A. Hicks.
- Summary
- "Securing the Safe Performance of Graphite Reactor Cores provides an account of the recent advances in securing safe performance of graphite-moderated nuclear reactors both within the UK and abroad which underpin life extension whilst maintaining high levels of plant performance. These reactors rely on graphite as a moderator in the form of layers of interlocked graphite bricks which undergo complex changes when exposed over long periods to the effects of neutron irradiation and radiolytic oxidation." "The book is a sequel to the successful RSC publication Managing of Ageing Processes in Graphite Reactor Cores, but with the emphasis on the challenges for the future safe performance. It is hoped that the contributed papers will also help in the design, construction, operation and eventual decommissioning of the new generation of graphite-moderated reactors. Papers presented in the book represent contributions from the most eminent specialists in the field and reflect the UK's contribution over the past 50 years to graphite reactor technology that will remain significant for years to come, especially in the development of Generation IV designs." "This seminal book is written in a way that takes the reader from fundamental knowledge to reactor operation in a straight forward and understandable manner - ideal for non-specialist as well as a unique reference for the specialist. It is fully illustrated to aid understanding and it is relevant to a wide range of readers from policy makers to reactor operators"--BOOK JACKET.
- Subject(s)
- ISBN
- 9781847559135 (hbk.)
1847559131 (hbk.) - Note
- "The proceedings of the meeting on Securing the Safe Performance of Graphite Cores held 24th-26th November 2008 at the University of Nottingham and run under the auspices of the British Carbon Group" --t.p. verso.
- Bibliography Note
- Includes bibliographical references and index.
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